A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory
Author:
Affiliation:
1. University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104
Funder
U.S. Department of Energy
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2021.1906585
Reference53 articles.
1. High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor
2. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
3. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion
4. MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7
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